COBRA-SFS Thermal-Hydraulic Analysis Code for Spent-Fuel Storage and Transportation Casks: Models and Methods
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چکیده
منابع مشابه
Thermal assessment of new Ignalina NPP casks for spent nuclear fuel storage at some abnormal conditions
For interim storage of spent nuclear fuel (SNF) at the Ignalina Nuclear Power Plant (INPP), the so-called “dry” storage technology has been chosen. In this case, SNF after a cooling (pre-storage) period in water pools (no less than 5 years) is placed into GNS (Germany) manufactured metal CASTOR ® RBMK-1500 or reinforced concrete CONSTOR ® RBMK-1500 casks and may be stored for at least 50 years ...
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*Correspondence: Xiaojing Liu, School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan Road, Shanghai 200240, China e-mail: [email protected] During the loss of coolant accident (LOCA) of supercritical water-cooled reactor (SCWR), the pressure in the reactor system will undergo a rapid decrease from the supercritical pressure to the subcritical condition. T...
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ژورنال
عنوان ژورنال: Nuclear Technology
سال: 2017
ISSN: 0029-5450,1943-7471
DOI: 10.1080/00295450.2017.1305190